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A kind of radioactive waste solidification treatment additive, preparation method and solidifying agent

A technology for radioactive waste and solidification treatment, applied in the field of radioactive waste solidification treatment additives, preparation methods, and curing agents, can solve the problems of low compressive strength, low leaching resistance, and large porosity, and achieve low porosity and improve stability. , the effect of increasing the compressive strength

Active Publication Date: 2022-07-01
NUCLEAR POWER INSTITUTE OF CHINA
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

[0007] The technical problem to be solved by the present invention is that the existing solidification additives for solidification of radioactive waste cannot meet the requirements of obtaining a stable and reliable solidified body with low porosity, and the radioactive waste is solidified by using the existing solidifying agent containing additives to obtain The solidified body has large porosity, low compressive strength, and low leaching rate. The purpose is to provide a solidification treatment additive for radioactive waste, a preparation method, a solidification agent and a solidification treatment method, which solve the above problems

Method used

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  • A kind of radioactive waste solidification treatment additive, preparation method and solidifying agent
  • A kind of radioactive waste solidification treatment additive, preparation method and solidifying agent
  • A kind of radioactive waste solidification treatment additive, preparation method and solidifying agent

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Effect test

Embodiment 1

[0033]a, preparation of additives: each component is uniformly mixed according to the following qualities: boric acid 65kg, sodium hydroxide 15kg, sodium tetraborate 3kg, sodium perborate 3kg, polyvinyl alcohol 1kg, dispersible latex powder 1kg, hydroxypropyl methyl alcohol 1kg of base cellulose; then high-temperature melting at a temperature of 250 ° C to obtain a polymeric borate additive, and the boron concentration of the polymeric borate is 150,000 mg / kg;

[0034] B, prepare cement base material: each component is uniformly mixed according to the following quality: cement 40kg, zeolite 16kg, calcium hydroxide 16kg, sodium metaaluminate 6kg, sodium sulfate 6kg;

[0035] c. Preparation of curing agent: the additive and the cement base material are mixed and stirred according to the mass ratio of 25:14, and heated to 40 ° C to obtain the curing agent of curable waste resin;

[0036] d. Curing waste resin: Stir the waste resin at a stirring speed of 30 r / min, add the curing a...

Embodiment 2

[0038] a, prepare additive: mix each component uniformly according to the following quality: boric acid 68kg, sodium hydroxide 18kg, sodium tetraborate 4kg, sodium perborate 4kg, polyvinyl alcohol 1.5kg, dispersible latex powder 1.5kg, hydroxypropyl alcohol 1.5kg of methyl cellulose; then high temperature melting at a temperature of 300 ° C to obtain a polymeric borate additive, the boron concentration of the polymeric borate is 200,000 mg / kg;

[0039] B, prepare cement base material: each component is uniformly mixed according to the following quality: cement 45kg, zeolite 18kg, calcium hydroxide 18kg, sodium metaaluminate 7kg, sodium sulfate 7kg;

[0040] c. Preparation of curing agent: Mix and stir the additive and the cement base material according to the mass ratio of 25:14, and heat to 50°C to obtain the curing agent for curable waste resin;

[0041] d. Curing the waste resin: Stir the waste resin at a stirring speed of 30 rpm, add the curing agent to the waste resin in ...

Embodiment 3

[0043] a, preparation additive: mix each component uniformly according to the following quality: boric acid 70kg, sodium hydroxide 20kg, sodium tetraborate 5kg, sodium perborate 5kg, polyvinyl alcohol 2kg, dispersible latex powder 2kg, hydroxypropyl methyl alcohol 2kg of base cellulose; then high-temperature melting at 400 ° C to obtain a polymeric borate additive, the boron concentration of the polymeric borate is 250,000 mg / kg;

[0044] B, prepare cement base material: each component is uniformly mixed according to the following quality: cement 50kg, zeolite 20kg, calcium hydroxide 20kg, sodium metaaluminate 8kg, sodium sulfate 8kg;

[0045] c. Preparation of curing agent: the additive and the cement base material are mixed and stirred according to the mass ratio of 25:14, and heated to 60°C to obtain the curing agent of curable waste resin;

[0046] d. Curing waste resin: Stir the waste resin at a stirring speed of 30 r / min, add the curing agent to the waste resin in 3 time...

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Abstract

The invention discloses a radioactive waste solidification treatment additive, a preparation method, a solidifying agent and an application. The solidification treatment additive comprises boric acid, sodium hydroxide, sodium tetraborate, sodium perborate, polyvinyl alcohol, dispersible latex powder, hydroxypropyl alcohol Base methyl cellulose, each component is melted at a high temperature of more than 200 degrees Celsius to obtain an additive, and the boron concentration of the additive is more than 100,000 mg / kg. The additive has a polymer chain structure, and forms a spatial network cross structure with calcium silicate hydrate generated by cement hydration, which strongly supports and fills the network structure. The curing agent prepared by this additive is used to solidify radioactive waste. , the radioactive waste can be wrapped in a more tightly closed space, the porosity of the solidified body can be reduced, the compressive strength of the solidified body containing the waste can be increased, and the anti-leaching rate of the solidified body can be reduced at the same time.

Description

technical field [0001] The invention relates to the technical field of radioactive waste treatment, in particular to a radioactive waste solidification treatment additive, a preparation method and a solidifying agent. Background technique [0002] During the operation of nuclear facilities, a large amount of low and medium radioactive wastes will be produced. Common wastes include steam residue, waste resin, waste filter elements and technical wastes. How to effectively dispose of these radioactive wastes is the key to the safe use of nuclear energy. Solidification technology is commonly used in the treatment of low and intermediate level waste, including cement solidification, asphalt solidification, glass solidification, etc. [0003] Asphalt solidification is the uniform mixing of asphalt and radioactive waste at a certain temperature to produce a saponification reaction, so that the radioactive waste is contained in the asphalt to form a solidified body. Asphalt solidi...

Claims

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Application Information

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Patent Type & Authority Patents(China)
IPC IPC(8): C04B24/38C04B28/02
CPCC04B40/0046C04B28/02C04B2111/00025C04B2111/00258C04B2201/50C04B2111/00017C04B22/0013C04B22/062C04B24/2623C04B24/383C04B2103/0057C04B14/047C04B22/064C04B22/08C04B22/147C04B18/0463
Inventor 王亚光张劲松陈云明曹骐梁帮宏鲁芸芸
Owner NUCLEAR POWER INSTITUTE OF CHINA